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    The Nuclear Fuel Cycle

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    Uranium

    URANIUM is a slightly radioactive metal that occurs throughout the earth's

    crust.

    It is about 500 times more abundant than gold and about as common astin.

    It is present in most rocks and soils as well as in many rivers and in sea

    water.

    Most of the radioactivity associated with uranium in nature is due to other

    materials derived from it by radioactive decay processes, and which are

    left behind in mining and milling.

    Economically feasible deposits of the ore, pitchblende, U3O8, range from

    0.1% to 20% U3O8.

    http://www.world-nuclear.org/info/inf14.html
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    Uranium Mining

    Open pit mining is used where deposits are close to the surface

    Underground mining is used for deep deposits, typically greater than 120m deep.

    Insituleaching (ISL), where oxygenated groundwater is circulated through a veryporous ore body to dissolve the uranium and bring it to the surface. ISL may useslightly acidic or alkaline solutions to keep the uranium in solution. The uranium isthen recovered from the solution.

    The decision as to which mining method to use for a particular deposit is governedby the nature of the ore body, safety and economic considerations.

    In the case of underground uranium mines, special precautions, consisting primarily

    ofincreased ventilation, are required to protect against airborne radiation exposure.

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    Uranium Mine in Niger (Sahara Desert)

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    Uranium Metallurgy

    Yellowcake

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    Yellowcake

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    More than 200 pounds of byproduct material, tailings, are typically produced for

    each pound of uranium.

    After extraction of uranium from the ore, the tailings contain much of their

    original radioactivity.

    Toxic heavy metals, including chromium, lead, molybdenum, and vanadium, are also

    present in this byproduct material in low, but significant, concentrations

    Tailings from Uranium Mining and Milling

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    Enriching Uranium for Reactor Fuel

    Increase the concentration of fissionable U-235 isotope

    Enrichment requires a physical process since

    U-235 and U-238 have the same chemical properties

    Physical processes require gases for separation

    Uranium and its oxides are solids

    Must convert uranium to UF6

    Enriched UF6 must be converted back to solid

    uranium or uranium oxide

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    or centrifugation

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    Enrichment

    The two method of uranium enrichment are:

    Gaseous diffusion (older)

    Centrifugation (newer)

    Both use small differences in the masses (< 1%) of the U-235F6 andU-238F6 molecules to increase the concentration of U-235.

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    F6

    F6

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    Centrifuge Enrichment

    FeedEnriched

    exitDepleted

    exit

    U235F6is lighter andcollects in the center

    (enriched)

    U238F6 is heavier and

    collects on the outsidewalls

    (Depleted/Tails)

    Feed toNext Stage

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    The gas centrifuge process has three characteristics that make it economicallyattractive for uranium enrichment:

    Proven technology: Centrifuge is a proven enrichment process, currently usedin several countries.

    Low operating costs: Its energy requirements are less than 5% of the requirementsof a comparably sized gaseous diffusion plant.

    Modular architecture: The modularity of the centrifuge technology allows for flexible

    deployment, enabling capacity to be added in increments as demand increases.

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    Fuel Fabrication

    Reactor fuel is generally in the form of ceramic pellets.

    These are formed from pressed uranium oxide which is sintered (baked)at a high temperature (over 1400C).

    The pellets are then encased in metal tubes to form fuel rods, which are

    arranged into a fuel assembly ready for introduction into a reactor.

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    UF6 Gas to UO2 Powder to Pellets

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    Fuel Pellets

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    Nuclear Fuel Assembly

    Fuel

    Pellet

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    Reprocessing: A Solution?

    Reprocessing: The chemical separation ofspent nuclear fuel into its major components.

    Wikipedia.org

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    Reprocessing

    Objectives

    Recover U, Pu and Th to be used as fuel

    Separate radioactive and neutron- absorbing

    fission products

    Convert the radioactive waste into suitable forms

    for safe storage

    The US does not have reprocessing nor a long

    term storage facility.

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    20

    Lawrence Livermore National Laboratory

    Reprocessing

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    Products of Reprocessing

    Uranium .6% U-235 and 99.4% U-238 Plutonium Minor Actinides

    Americium

    Major long-term heat source Neptunium

    Major source of radiation

    Curium

    Fission Products

    Strontium-90, Cesium-137 Generate large amounts of heat for the first 50-80 years after disposal Removal from the repository would reduce the amount of space needed

    Iodine-129, Technetium-99 Mobile isotopes that can easily travel through geological formations

    Major contributors of radiation to biosphere

    U.S. DOE

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    Three Nuclear Fuel Cycles

    Once through thermal reactors

    (current approach)

    Recovery of plutonium for one additional

    pass through thermal reactors

    Repeated reprocessing and recycling ofuranium, plutonium, and other

    transuranics in fast-neutron reactors

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    Why Reprocess and Recycle?

    Original reason (1940s-1970s):

    Believed demand for nuclear power would be far greater than it

    turned out to be Believed world uranium reserves were far smaller than they

    turned out to be

    Current reason:

    Reduce amount of nuclear waste

    Given the uncertainties surrounding the Yucca Mountainlicense application process

    Additional uranium energy secondary

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    Spent Fuel Storage Pools

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    Reprocessing: Methods/Techniques

    PUREX: Plutonium and Uranium Extraction Most widely used method

    Results in a pure stream of plutonium

    UREX: Uranium Reduction Extraction

    Replacement for PUREX Results in pure uranium stream

    The plutonium remains mixed with the fissionproducts and minor actinides

    UREX+ Refinement of the UREX process

    Pyroprocessing Reduces the liquid waste that remains in the UREX

    process

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    Reprocessing: Then what?

    Storage in a repository, or . . .

    . . . Waste Recycling

    Definition: Transmuting or destroying the separatedwaste products of reprocessing. Transforms the long-lived radionuclides into short-lived ones. 12

    Reprocessing alone is not sufficient to reduce thevolume and toxicity of used fuel, ensure adequatesupplies of uranium, and achieve proliferation resistance.

    A transmutation program could transform the problem oflong-term isolation in a geological repository (for 10s ofthousands of years) to a less difficult problem of storagefor several decades or a few hundred years.

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    Methods of Recycling

    Transmutation involves inducing nuclear

    reactions in some form of non-traditional

    reactor.

    Fast reactors

    Breeder Reactors

    Burner reactors

    Fast Neutron Reactors

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    Results of Recycling

    Waste products:

    No transmutation scheme is able to destroy

    all of the components of spent nuclear fuel.

    Most will require multiple passes through thereactor to recycle a significant amount.

    Some of the components, although reduced

    by volume, will be converted to moreradioactive forms.

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    Benefits of Reprocessing andRecycling

    The ability to reduce the volume and toxicity

    of nuclear waste

    A smaller, simpler repository Extension of time before a second repository is

    necessary

    Closed fuel cycle consistent uraniumsupply

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    Costs of Reprocessing

    Plutonium Stockpiles/WeaponsProliferation

    Environmental and health harms

    Terrorism Transportation of high level waste

    Reactor safety, worker health

    Economic cost

    New regulatory schemes

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    Mixed Oxide Fuel (MOX)

    MOX is produced from the output of reprocessing plants and is a mixture of

    plutonium and uranium oxides with a composition of 3% to 7% PuO2 and the rest

    UO2

    . The MOX is then mixed with ordinary LEU uranium-oxide fuel for use in light

    water reactors. Mixture is 1/3 MOX and 2/3 LEU.

    By 2001, over 20 power reactors in France were using MOX for one third of their

    fuel In the US, MOX fuel is being used as a means of disposing of Pu from

    dismantled nuclear weapons in the US and Russia.

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    Fuel Reprocessing Plant, Marcoule, France

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    Relative Costs

    Process $/kg fuel

    Uranium $500

    Conversion $50

    Enrichment $600

    Fabrication $250

    Wet storage Included in capital & O%M

    Dry cast storage $200

    Geological storage $400

    Total Cost $2000